VVER-1000 neutronics calculation with ENDF/B-VII data

被引：8

作者：

Mahlers, Y. P. ^{[1
]}

机构：

[1] Inst Nucl Res, UA-03680 Kiev, Ukraine

来源：

ANNALS OF NUCLEAR ENERGY | 2009年 / 36卷 / 08期

关键词：

D O I：

10.1016/j.anucene.2009.04.002

中图分类号：

TL [原子能技术]; O571 [原子核物理学];

学科分类号：

0827 ; 082701 ;

摘要：

The initial release of the ENDF/B-VII nuclear data library is verified for VVER-1000 reactors. For neutronics calculation, the MCNP code based on the Monte-Carlo method is applied. Continuous-energy cross-sections for use with MCNP are calculated with the NJOY code. Isotopics for burned fuel is calculated with the WIMSD code. Calculated criticality, pin-to-pin power distribution, time-dependent critical concentration of soluble boron, worth of the control rods, average fuel assembly powers and time-dependent axial power distribution are compared to the corresponding experimental values for both zero-power VVER-1000 model, created at the LR-0 experimental facility, and the first fuel cycle of a real VVER-1000 reactor. For all of these parameters, neutronics calculation with ENDF/B-VII is in good agreement with the measurement. Moreover, for VVER-1000 neutronics calculation, ENDF/B-VII provides better results than ENDF/B-VI. (C) 2009 Elsevier Ltd. All rights reserved.

引用

页码：1224 / 1229

页数：6

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